• 한국전산유체공학회:학술대회논문집
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• 2010.05a
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• pp.181-186
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• 2010

A numerical study was conducted to predict the performance curve of a canned motor pump for SMART(System Integrated Modular Advanced ReacTor). The study used a computational domain which included not only the pump but also a suction pipe and a volute casing with a discharging pipe in order to simulate an experimental setup. The ANSYS CFX program was utilized to obtain flow characteristics inside the pump as well as the overall pressure rise across the pump operating on- and off-design points. Computed results showed that the performance of the pump at off-design points was much lower than expected. Special attention was made to find the cause of the low performance of the pump operating at low flow rate.

• Nuclear Engineering and Technology
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• v.49 no.5
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• pp.968-978
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• 2017

Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermal-hydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are slightly different during the early stage of the transient after a break simulation. A safety injection using a high-pressure pump effectively cools down and recovers the inventory of a reactor coolant system. The global trends show reproducible results for an SBLOCA scenario with three different break locations. It was confirmed that the safety injection system is robustly safe enough to protect from a core uncovery.

• Proceedings of the Korean Operations and Management Science Society Conference
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• 2004.05a
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• pp.197-200
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• 2004

기존의 제어실 정보표시는 계통 및 기기정보를 바탕으로 하는 사건중심의 나열식 정보표시체계를 가지므로써 운전원이 표시되는 정보를 검색하고 판단하기까지는 많은 정신적 부담이 있었으며 이로 인한 운전오류가 많이 발생하였다. 이에 따라 본 논문은 일체형원자로(SMART:System-integrated Modular Advanced ReacTor) 제어실에서 운전원이 감독자 기능을 지원할 수 있도록 운전원이 쉽고 빠르게 필요한 운전정보를 검색하여 필요한 조치를 취할 수 있는 정보체계를 제안한다.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.19-26
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• 1998

Nuclear design bases for System-Integrated Modular Advanced ReacTor(SMART) core are presented. Based on the proposed design bases, a SMART core loading pattern is constructed and its nuclear characteristics are studied. The proposed core loading pattern satisfies 3-year cycle length and soluble boron-free operation requirements at any time during the cycle

• Proceedings of the Korean Operations and Management Science Society Conference
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• 2004.05a
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• pp.5-8
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• 2004

컴퓨터기반 운전지원시스템은 운전원의 발전소 상태감시와 진단기능을 수행을 지원하여 운전원의 안전성을 향상시키는 시스템으로 80년대 중반부터 개발되어왔고, 또한 최근의 컴퓨터 기술과 도구의 빠른 발전으로 컴퓨터기반 운전지원 시스템의 개발 및 원전 적용에 대한 연구가 이루어지고 있다. 본 논문에서는 컴퓨터기반 운전원 조언 시스템의 기술 현황을 분석하고, 현재 설계를 진행중인 일체형원자로(SMART, System-integrated Modular Advanced ReacTor)에 컴퓨터기반 운전지원 시스템 적용을 위한 개발방안을 제안한다.

• Nuclear Engineering and Technology
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• v.52 no.8
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• pp.1834-1846
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• 2020

The SMART (System-integrated Modular Advanced ReacTor) is an integral-type small modular reactor developed by KAERI (Korea Atomic Energy Research Institute). This paper discusses the development of a dynamic equivalent model of the SMART control rod drive mechanism that can be efficiently utilized for complicated analysis during the design of the SMART. A semi-empirical approach is used to develop the equivalent model; that is, the equivalent model is defined analytically and verified empirically. Two types of tests, dynamic characteristics tests and seismic loading tests, are conducted for the development and verification of the dynamic equivalent model, respectively. Acceleration response spectra from the seismic analysis based on the developed equivalent model show good agreement with those from the seismic loading tests.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.606-611
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• 1998

330MWt 출력의 신형 원자로인 SMART(System integrated Mod씰w Advanced ReacTor)가 전기 생산뿐만 아니라 해수의 담수화를 위한 에너지 공급을 위해 한국원자력연구소에 의해 개발되고 있다. SMART의 원자로 압력용기에서의 중성자 조사량을 기존의 각분할법 코드 대신에 몬데칼로 수송 코드인 MCNP-4A를 이용하여 평가하였다. MCNP-4A에 의한 몬데 칼로 모사는 각분할법에 비해 핵 단면적 자료, 선원항, 그리고 기하학적 모델링의 문제로부터 야기되는 불확실성을 감소시킬 수 있을 뿐만 아니라 초기 개념 설계 단계에서 상세 노심 출력 분포 자료에 의존하지 않고 선원항을 평가할 수 있는 장점이 있다. 본 연구에서는 원자로 압력 용기 내부의 원자로 노심 및 다른 구조물을 포함하는 전체 원자로 구조에 대하여 몬테 칼로 모사를 적용하였다. 1단계에서는 임계도 계산에 의해 선원항으로 이용되는 원자로 노심내의 열 출력 분포를 평가하고, 2단계에서는 노심내의 열 출력 분포를 고정 선원으로 이용하여 압력 용기에서의 중성자 조사량을평가하였다. 그 결과 SMART 압력용기의 중성자 조사량은 규제 요건을 만족하는 것으로 나타났다.

• 한국전산유체공학회:학술대회논문집
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• 1998.05a
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• pp.75-81
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• 1998

A new advanced integral reactor of 330 MWt capacity named SMART(System-integrated Modular Advanced ReacTor) is currently under development at KAERI(Korea Atomic Energy Research Institute). One of the major design features of the integral reactor is locating the steam generators(SG) inside reactor vessel and eliminating the possibility of LB LOCA(large Break Loss of Coolant Accident). Orifices are fitted at the low part of steam generator cassette to stabilize and balance coolant flow distribution in the MCP (Main Circulation Pump) pressure header. A sensitivity analysis is conducted to determine the optimum orifice size using computer code 'CFX'.

• Tribology and Lubricants
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• v.18 no.2
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• pp.105-108
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• 2002

Specially designed grooved journal bearings are installed in the main coolant pump for SMART (System-integrated Modular Advanced ReacTor) to support radial load on the rotating shaft. The canned motor type main coolant pumps are arranged vertically on the reactor vessel and filled with circulating primary coolant which is pure water. The main coolant pump bearings are lubricated with this coolant without any other external lubricant supply. Because lubricating condition is too severe for this bearing to generate proper hydrodynamic film, investigation of lubrication characteristics of the journal bearing is important to satisfy life constraint of whole pump system, and the results will be applied to the analysis of dynamic characteristics of the shaft system. The bearing is made of silicon graphite which has self$.$lubricating effect. A lubrication analysis method is proposed for this vertically grooved journal bearing in the main coolant pump of SMART, and lubricational characteristics of the bearings are examined in this paper.

• Nuclear Engineering and Technology
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• v.33 no.1
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• pp.111-120
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• 2001

In this study, a dynamic analysis of the integral reactor SMART (System-integrated Modular Advanced ReacTor) under postulated seismic events is performed to review the response characteristics of the major components. To enhance the feasibility of an analysis model, a detailed finite element model is synchronized with the products of concurrent design activities. The artificial time history, which has been applied to the seismic analysis for the Korean Standard Nuclear Power Plant (KSNP), is chosen to envelop broad site specifics in Korea. Responses in the horizontal direction are found slightly amplified, while those in the vertical direction are suppressed. Since amplified response is monitored at the control element drive mechanism (CEDM), minor design provision is considered to enhance the integrity of the subsystem.